1. HWK NSTX PAC19, Feb. 22-24, 2006 1 Reduced Recycling from Lithium Coatings: Recent Results and Future Plans Supported by Office of Science Culham Sci Ctr U St. Andrews York U Chubu U Fukui U Hiroshima U Hyogo U Kyoto U Kyushu U Kyushu Tokai U NIFS Niigata U U Tokyo JAERI Hebrew U Ioffe Inst RRC Kurchatov Inst TRINITI KBSI KAIST ENEA, Frascati CEA, Cadarache IPP, Jülich IPP, Garching ASCR, Czech Rep U Quebec College W&M Colorado Sch Mines Columbia U Comp-X General Atomics INEL Johns Hopkins U LANL LLNL Lodestar MIT Nova Photonics New York U Old Dominion U ORNL PPPL PSI Princeton U SNL Think Tank, Inc. UC Davis UC Irvine UCLA UCSD U Colorado U Maryland U Rochester U Washington U Wisconsin H. W. Kugel NSTX PAC 19th Meeting Feb. 22-24, 2006, PPPL Princeton Plasma Physics Laboratory On behalf of the NSTX National Team

2. HWK NSTX PAC19, Feb. 22-24, 2006 2 Lithium Research Motivation and Goals TFTR demonstrated benefit of partial Li coating on graphite PFCs Strong edge pumping (reduction of recycling) Improvement in energy confinement (x2) CDX-U found lithium PFC’s yielded ~30% recycling coefficient up to an order of magnitude increase in confinement times (exceeded ITER98P(y,1) scaling by 2 - 4  ) very high power handling capability (~50 MW/m 2, 300 s ) NSTX in FY05 used Lithium Pellet Injection (LPI) to create coatings that significantly edge pumped neutral beam-heated plasmas. NSTX is preparing for early FY06 a Lithium Evaporator for routine thick lithium coatings over a significant fraction of the PFCs: Will provide density control for long-pulse operation

3. HWK NSTX PAC19, Feb. 22-24, 2006 3 NSTX Lithium Research Applications to ST, ITER and Demo Lithium PFCs for High Power ST Allow very high power handling capability for high P/R divertors Lithium PFCs for ITER and DEMO ITER and DEMO continuous long pulse operation is not possible with the planned Be, C, and W PFC’s Future lithium flow concepts could remove tritium, provide high power handling, and avoid other PFC issues associated with Be, C, and W PFC’s

4. HWK NSTX PAC19, Feb. 22-24, 2006 4 NSTX FY05 Density Control Experiments Guided by the TFTR Lithium Experience 1)Center Stack Limited discharges (CSL) and Lower Single Null (LSN) discharges were used 2)Ohmic Helium Conditioning discharges were used to degas the Center Stack (Exp-1 & Exp-2) and the Lower Divertor (Exp-3) 3)Lithium Pellets were injected into CSL and LSN Ohmic Helium discharges to coat the plasma wetted surfaces and prevent lithium saturation by the fuel gas 4)Then CSL, and LSN low density, deuterium NBI reference plasmas were applied to measure recycling changes due to lithium pumping of the edge plasma Low density reference plasmas were used to avoid saturating the available lithium pumping capacity

5. HWK NSTX PAC19, Feb. 22-24, 2006 5 Exp-1: Initial CSL NBI Deuterium Reference Shot Following 30 mg of Lithium Deposition on CS Exhibited ~x3 Decrease in Density and Peaked Profiles Li pumping of edge density saturated after the 3 Reference Discharges consistent with the consumption of the deposited lithium. ~30 mg Li = 2.6x10 21 Li atoms available to react with 2.6x10 21 D ~9x10 20 D/Shot, and Li pumping stops ~2-3 shots (1.8-2.7x10 21 D removed) Center-stack limiter discharges, 0.9 MA, 0.45T, D 2 gas fueling 3.5mg

6. HWK NSTX PAC19, Feb. 22-24, 2006 6 25 mg of lithium pumping of edge density saturated after the 3 Reference Discharges and returned to pre Li wall conditions Expected if most injected gas reacts with the deposited lithium Exp-3:LSN NBI D Reference Shot Following 25 mg of Li Deposition on Lower Divertor Exhibited ~x2 Decrease in Density and Peaked Profiles Lower single-null divertor discharges, 0.45T, D 2 gas fueled 3.5mg

7. HWK NSTX PAC19, Feb. 22-24, 2006 7 The Next Step: Lithium Evaporator (LITER-1) Being Readied for Density Control for Long-pulse Operation Li evaporation rate ~ 50 mg/min Compare to 25, 2mg Li pellets Good Lower Divertor Region Coverage Evaporated lithium films intended to reduce recycling and improve particle control beyond levels achieved with LPI

8. HWK NSTX PAC19, Feb. 22-24, 2006 8 LITER-1 Status: Off-line Testing & Calibration in Progress for Installation During Week of 2/27/06 Thickness of lithium deposited on NSTX plasma facing components controlled by varying temperature of lithium oven LITHIUM OVEN EXIT APERTURE (“SNOUT”) LITER-1 “MOCKUP” INSIDE NSTX GAP IN COPPER DIVERTOR BACKPLATE AND CARBON TILES LITER-1 TIP GRAPHITE PLASMA- FACING TILE BAFFELED LITHIUM RESERVOIR

9. HWK NSTX PAC19, Feb. 22-24, 2006 9 Experimental Plan (XP) for Investigation of Density Control Using Evaporated Coatings XP601: “Effect of Evaporated Lithium PFC Coatings on Density Control” will investigate the effects of evaporated lithium coatings on density control prior to its application in other XP's. First, this XP will make contact with the LPI thin coating results, and then proceed to thicker coatings and long pulses. The basic sequence of XP601 will characterize: 1. Thin coatings on conditioned & unconditioned surfaces for comparison with LPI coatings – L-mode (day 1) 2. Thin coatings to achieve H-mode, same shape as above (day 2) 3. Thick coatings to achieve H-mode, same shape as above (day 2) 4. Thin/thick coatings for density controlled long pulse, LSN H-mode (day 3) 5. Thin/thick coatings for density controlled L-mode for transport and turbulence experiments (day 3)

10. HWK NSTX PAC19, Feb. 22-24, 2006 10 Preparations for Upgrading Fueling Capability to Accommodate Lithium Edge Pumping Gas Injection System Fueling Test present Low Field Side gas injection systems at higher pressures Test High Field Side-midplane gas injection system at the same higher pressure and increase its plenum capability ~x4-5 Install 3 injectors in parallel at Bay-J top Supersonic Gas Injector Fueling SGI on a movable probe commissioned and operated on NSTX Used to fuel ohmic and 2-6 MW NBI-heated L- and H-mode plasmas Measured fueling efficiency 0.1 - 0.3 New larger plenum and multi-pulse capability installed May install separate dedicated fueling line for high pressure operation

11. HWK NSTX PAC19, Feb. 22-24, 2006 11 Lithium Tokamak With Core Fueling Leads To a Simple, Compact Component Test Facility Entire CTF plasma CTF with TF, PF and blanket comparable in volume to present- day light water fission reactor pressure vessel (~100 m 3 ) L. Zakharov  PFC: 0.1-0.5 mm “creeping” lithium film in porous moly or tungsten surface  Required replacement rate: ~10 liter/hour (flow rate < 1 cm/sec) for ITER  Small size = access for core fueling with low voltage NBI  R 0 =1.25m, a=0.75m, A=1.66,  =2, 3T, 11 MA  At 40% , P fusion =400 MW (~ITER)  Plasma volume =26 m 3 (3% of ITER)  Manageable tritium requirements for reactor development

12. HWK NSTX PAC19, Feb. 22-24, 2006 12 Conclusions NSTX lithium research for recycling control and performance improvement is unique and has applications to high power ST, ITER, and Demo NSTX thin coating Li Pellet Injection experiments demonstrated that surfaces pre-coated with lithium edge pumped a diverted plasma The results are consistent with the consumption of the deposited lithium A Lithium Evaporator is in preparation for routine thick lithium coatings over a significant fraction of the PFCs for experiments in early 2006 to provide density control for long-pulse operation The results will be used for Decision Analysis on edge pumping (e.g., enhanced lithium capability and/or cryopumping) and core fueling (e.g., D Pellet Injection and/or Compact Torus Injection)